Prioritizing pressure drop research in nuclear thermal hydraulics

Q Cai, F D'Auria, K Umminger, D Bestion… - Progress in Nuclear …, 2022 - Elsevier
Prediction of pressure drop by wall friction and at geometric discontinuities is important in
nuclear thermal hydraulics simulation. Pressure-drop models were established and …

Research progress on thermal hydraulic characteristics of spent fuel pools: A review

C Xu, Z Wang, S Tang, X Chi, X Zhu, Y Li, N Wang - Energies, 2023 - mdpi.com
Nuclear power plants (NPPs) produce large amounts of spent fuel while generating
electricity. After the spent fuel is taken out of the reactor core, it still has a high decay heat …

Modelling fuel assembly flow nozzles in a spent nuclear fuel dry cask using CFD codes

A Hernandez-Avellaneda, G Jimenez, L Rey… - Annals of Nuclear …, 2023 - Elsevier
Abstract Computational Fluid Dynamic (CFD) codes are a widely used tool in spent nuclear
fuel dry storage systems applications. A recurrent simplification used in most spent nuclear …

Evaluation of existing correlations and development of a new correlation for single-phase friction factor in rod bundle assembly

VS Chalgeri, X Shen, T Yamamoto - Annals of Nuclear Energy, 2024 - Elsevier
Single-phase water flow in rod bundles plays a crucial role in removing the heat generated
in the nuclear reactor core. The design and safety analysis of light-water nuclear reactors …

Development of friction factor correlations for hexagonal and square bundles with rough rods based on CFD

M Liu, X Wang, S Ni, L Liu, H Gu - Annals of Nuclear Energy, 2022 - Elsevier
Abstract Changes in fuel assembly roughness caused by crud deposits can influence the
flow resistance characteristics of the fuel assembly. The existing correlations cannot …

Experimental study on the natural circulation behavior of a full-scale PWR fuel assembly

M Liu, S Ni, X Wang, L Liu, H Gu - Annals of nuclear energy, 2022 - Elsevier
During a loss-of-coolant accident in spent fuel pools, the fuel assembly will be exposed to
the air environment and decay heat will be removed through the natural circulation of air …

Investigation on turbulent heat transfer to lead-bismuth eutectic flows in rough rod bundles for nuclear applications

X Wang, M Liu, R Zhang, J Fu, T Cong, H Gu - International Journal of …, 2024 - Elsevier
Liquid lead-bismuth eutectic corrosion and the deposition of corrosion particles can lead to
surface roughening of rod bundles, which impacts the convective heat transfer …

Natural convection through and over a heating porous medium: Towards high fidelity simulations of nuclear spent fuel pools

V Hamtiaux, P Ruyer, Y Bartosiewicz - … Journal of Heat and Fluid Flow, 2025 - Elsevier
This paper presents a numerical investigation involving Direct Numerical Simulations (DNS)
of natural convection occurring within mixed domains of porous and pure fluids, featuring an …

Development of analytical models for the natural circulation behavior of a full-scale PWR fuel assembly

M Liu, S Ni, X Wang, L Liu, H Gu - Annals of Nuclear Energy, 2022 - Elsevier
During a loss-of-coolant accident in spent fuel pools, the fuel assembly will be exposed to
the air environment and decay heat will be removed through the natural circulation of air. In …

Development of Nusselt number and friction factor models for rough rod bundles based on wall functions

X Wang, M Liu, X Yan, T Cong, H Gu - Annals of Nuclear Energy, 2024 - Elsevier
The fuel assembly in the reactor undergo surface roughening due to fouling deposits and
material corrosion, which significantly impact the pressure drop and convective heat transfer …